Semiscale secondary transient investigations: results from Semiscale MOD-2C feedwater and steam line break tests

Conference · Mon Dec 31 23:00:00 EST 1984

OSTI ID:6188906

Boucher, T J

A series of experiments was conducted in a scaled model of a pressurized water reactor (Semiscale MOD-2C) to investigate the system response to steam generator main steam line and bottom main feedwater line breaks. The two main steam line break tests simulated double-ended offset shears upstream and downstream of the flow restrictor. The three bottom main feedwater line break tests simulated 100% (percentage of feedwater distribution box outlet flow area), 50%, and 14.3% breaks downstream of the check valve. From the experimental results, the characteristic system responses for these secondary transients have been examined. Experimental results are compared to Find Safety Analysis Report code calculation assumptions regarding separator performance during steam line breaks and primary-to-secondary heat transfer degradation with loss of mass during feedwater line breaks. Finally, the results are discussed with respect to current safety concerns regarding pressurized thermal shock and primary overpressurization phenomena.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6188906
• Report Number(s): EGG-M-20885; CONF-8510173-52; ON: DE86005312
• Country of Publication: United States
• Language: English

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